[2I06-07] Fusion Reactor System, Design, Application

11:35 AM - 11:50 AM JST(2:35 AM - 2:50 AM UTC)

[2I07] Tritium breeding scenario of laser inertial fusion reactor with reduced-tritium fuel

*Kaoru Omiya¹, Tomoyuki Johzaki², Kanta Utsumi¹, Kazuki Matsuo³, Masatoshi Kondo¹ (1. Science Tokyo, 2. Hiroshima Univ., 3. EX-Fusion)

Keywords:

Laser fusion reactor,Liquid blanket,Tritium breeding,System dynamics,LiPb

The purpose of this study is to clarify the operation scenarios of laser fusion reactors with reduced-tritium fuel by using system dynamics (SD) simulation. Using a lithium-lead alloy with 25 mol% natural lithium (Lithium Enhanced Lithium Lead Alloy: LELLA), the blanket full coverage TBR can be 1.47 with a 7 m chamber diameter and 1.5 m blanket thickness. Fuel burn calculations showed fusion reaction improved when the reduced-tritium fuel has a deuterium to tritium ratio of 1:1. Through SD simulation, we evaluated the days needed to reach steady-state operation using reduced-tritium fuel. We also examined the amount of T accumulation in the LELLA blanket and the time required for continuous extraction.